• Nuclear Engineering and Technology
• /
• 제55권11호
• /
• pp.4026-4031
• /
• 2023

In this article, we report a new empirical formula for quick calculation of cross sections of (n, α) reactions with 14-15 MeV neutrons. Cross sections are analysed in terms of the compound nucleus model. A systematic trend for 14-15 MeV neutrons is found in the variation of (n, α) reaction cross sections with the parameters (N - Z + 1), (E_n + Q)^0.5 and N/Z. The empirical relation between the cross sections and these parameters has been obtained, which give fairly good fits with the experimental data. We have also investigated the odd-even effects on (n, α) cross sections considering binding energy systematic of the shell model. The present formula is very useful in predicting of the (n, α) cross sections, where the measurements are not available as well as in testing new experimental data.

• Nuclear Engineering and Technology
• /
• 제46권3호
• /
• pp.281-290
• /
• 2014

In order to properly quantify fission reactor neutronics parameter uncertainties, we have to use covariance data and sensitivity profiles consistently. In the present paper, we establish two consistent methodologies for uncertainty quantification: a self-shielded cross section-based consistent methodology and an infinitely-diluted cross section-based consistent methodology. With these methodologies and the covariance data of uranium-238 nuclear data given in JENDL-3.3, we quantify uncertainties of infinite neutron multiplication factors of light water reactor and fast reactor fuel cells. While an inconsistent methodology gives results which depend on the energy group structure of neutron flux and neutron-nuclide reaction cross section representation, both the consistent methodologies give fair results with no such dependences.

• 한국자동차공학회논문집
• /
• 제8권6호
• /
• pp.165-175
• /
• 2000

In order to improve the function of a door seal, its section design technique is discussed in this study, Its roles are prevention of an inflow of dusts, noise interception, insulation, wateproof, and the vibroisolating action which reduces vibration between the body and the door of a car while running, and the buffer action which sustain the proper reacting force as the door is closed. In this study, the optimal cross section of a door seal is designed using nonlinear finite element analysis (commercial finete element analysis program EASi-SEAL) and tables of orthogonal arralys with respect to relations between door and door seal to secure the satisfactory airtight property with the minimum force to shut the door.

• Nuclear Engineering and Technology
• /
• 제52권12호
• /
• pp.2717-2724
• /
• 2020

Silicon, especially silicon in the form of SiO₂, is a major component of rocks. Final spent fuel storages, which are being designed, are located in suitable rock formations in the Earth's crust. Reduction of the uncertainty of silicon neutron scattering and capture is needed; improved silicon evaluations have been recently produced by the ORNL/IAEA collaboration within the INDEN project. This paper deals with the nuclear data validation of that evaluation performed at the LR-0 reactor by means of critical experiments and measurement of reaction rates. Large amounts of silicon were used both as pure crystalline silicon and SiO₂ sand. The critical moderator level was measured for various core configurations. Reaction rates were determined in the largest core configuration. Simulations of the experimental setup were performed using the MCNP6.2 code. The obtained results show the improvement in silicon cross-sections in the INDEN evaluations compared to existing evaluations in major libraries. The new Thermal Scattering Law for SiO₂ published in ENDF/B-VIII.0 additionally reduces the discrepancy between calculation and experiments. However, an unphysical peak is visible in the neutron spectrum in SiO₂ obtained by calculation with the new Thermal Scattering Law.

• 한국지반공학회논문집
• /
• 제36권1호
• /
• pp.29-38
• /
• 2020

최근 환기구, 비상탈출용 수직구, 취수탑 가시설 등 지중 가물막이 또는 차수벽체로 원형 가물막이가 많이 적용되고 있다. 원형단면의 경우 벽체에 작용하는 토압이 원형가물막이 형상에 따라 아칭효과(arching effect)로 인하여 작용토압에 대한 구조체의 부재력이 감소하는 것으로 알려져 있다. 본 연구에서는 원형 가물막이에 대한 2D 유한요소해석(FEM)을 활용하여 원형띠장(ring beam) 강성을 산출 후 탄소성해석에 적용하여 부재의 단면력을 검토하였다. 더불어 3D 유한요소해석(FEM)을 통하여 원형단면의 가물막이가 다각형 형태의 가물막이보다 전단력, 휨모멘트, 그리고 발생변위가 최소값을 갖는 것으로 나타났으며, 이로써 원형단면 가물막이가 구조적으로 보다 효율적인 단면 형태임을 확인하였다

• Nuclear Engineering and Technology
• /
• 제52권4호
• /
• pp.791-796
• /
• 2020

Nuclear fusion seems to be a good choice of energy source in the future. Nickel is one of the crucial structural materials for fusion devices. In this work, the cross section data of ⁵⁸Ni(n,p)⁵⁸Co, ⁶⁰Ni(n,p)⁶⁰Co, ⁶¹Ni(n,p)⁶¹Co, ⁶²Ni(n,p)⁶²Co and ⁶⁴Ni(n,p)⁶⁴Co reactions were calculated using the nuclear codes ALICE/ASH, EMPIRE 3.2 and TALYS 1.8. In addition, the cross sections were calculated with the empirical formulas obtained in our previous paper at 14-15 MeV. The obtained results were compared with the measured values in the literature, and with the evaluated data files (JEFF-3.3, TENDL-2017, ENDF/B-VIII.0).

• 한국방사선학회논문지
• /
• 제15권2호
• /
• pp.257-263
• /
• 2021

본 연구는 한국원자력연구원에서 보유하고 있는 100 MeV 선형가속기를 사용하여 천연텅스텐과의 핵반응으로 부터 발생시켜 발생되는 감마선을 측정하여 natW(p,xn)176Re 핵반응에 대한 상대핵반응단면적을 도출하였다. 일반적으로 반감기가 짧은 동위원소에 대한 연구는 항상 짧은 시간 내에 방사능의 강도가 급격하게 작아지는 경향을 보이기 때문에 측정자체가 매우 어려운 것이 현실이다. 특히 176Re의 경우는 반감기가 5.3 분으로 상대적으로 매우 짧은 방사성핵종 중의 하나이다. 본 연구에서는 이런 짧은 반감기를 가지는 176Re 동위원소로부터 발생되는 109.08 keV 감마선을 고순도 Ge검출기를 이용하여 측정하였다. 얻어진 상대 측정값들은 1967년에 Richard G.에 의해 발표된 8 ~ 14 MeV 양성자에너지 영역에서의 결과와 이를 기반으로 계산에 의한 핵반응단면적에 대한 평가한 2019년 A. J. Koning의 결과인 TENDL-2019값과 비교분석하였다. 이 연구의 결과는 미래의 에너지원으로 알려져 있는 핵융합로의 설계, 천체 물리학, 핵의학 및 양성자치료 분야에 요긴하게 활용될 것으로 생각된다.

• 한국콘텐츠학회논문지
• /
• 제4권2호
• /
• pp.76-82
• /
• 2004

기존의 $^{141}$Pr(n,$\gamma$)$^{142}$Pr 반응에 대한 열중성자포획단면적 결과들은 여러 종류의 값들이 보고 되어 있다. 본 연구에서는 이상적인 중성자속을 가지는 교토원자로실험소의 중수열중성자장치를 이용하여 방사화 방법을 통해 열중성지포획 단면적을 보다 정밀하게 측정하였다. 시료에 입사되는 열 중성자속은 $^{197}$Au(n,${\gamma}$)$^{198}$Au 반응을 통하여 측정되었다. 측정된 결과는 기존의 측정 결과 및 JENDL-3.2, ENDF/ B-VI, JEF-2.2의 평가치들과 비교하였다.

• Bulletin of the Korean Chemical Society
• /
• 제31권4호
• /
• pp.989-998
• /
• 2010

The titled dye of DBPI gives amplified spontaneous emission (ASE) with maximum at 580 nm upon pumping by nitrogen laser (${\lambda}_{ex}\;=\;337.1\;nm$). The ground state absorption cross section (${\sigma}_A$) and emission cross section (${\sigma}_E$) as well as effective emission cross section(${\sigma}^*_E$) have been determined. The electronic absorption spectra of DBPI were measured in ethanol and tetrahydrofuran at room and low temperature. DBPI displays molecular aggregation in water. The photochemical reactivity of DBPI was also studied in carbon tetrachloride upon irradiation with 525 nm light. The electrochemical investigation of DBPI dye has been carried out using cyclic voltammetry and convolution deconvolution voltammetry combined with digital simulation technique at a platinum electrode in 0.1 mol/L tetrabutyl ammonium perchlorate (TBAP) in two different solvents acetonitrile ($CH_3CN$) and dimethylformamide (DMF). The species were reduced via consumption of two sequential electrons to form radical anion and dianion (EE mechanism). In switching the potential to positive direction, the compound was oxidized by loss of two sequential electrons, which were followed by a fast dimerization and/or aggregation process i.e $EC_{dim1}EC_{dim2}$ mechanism. The electrode reaction pathway and the chemical and electrochemical parameters of the investigated compound were determined using cyclic and convolutive voltammetry. The extracted electrochemical parameters were verified and confirmed via digital simulation method.

• Journal of Radiation Protection and Research
• /
• 제41권3호
• /
• pp.286-290
• /
• 2016

Background: Activation of air and water in the electron linear accelerator for medical use has not been considered severely. By the new Japanese regulation for protection of radiation hazard, it became indispensable to evaluate of activation of air and water in the accelerator room. The measurement of induced activity in air and water components in the electron energy region of 10 to 20 MeV is very difficult, because this energy region is close to the threshold energy region of photonuclear reactions. Then, we measured the photonuclear reaction yields of $^{13}N$, $^{15}O$, and $^{11}C$ by using the electron linear accelerator. Obtained data were compared with the data calculated by the Monte Carlo method. Materials and Methods: An activation experiment was performed at the Research Center for Electron Photon Science, Tohoku University. Highly purified $SiO_2$, $Si_3N_4$, and carbon disks were irradiated for 10 minutes by bremsstrahlung converted by a tungsten plate. Induced activity from C, N, and O was obtained. Monte Carlo calculation was performed using MCNP5 and AERY (DCHAIN-SP) to simulate the experimental condition. Cross section data were adopted the KAERI dataset. Results and Discussion: In our experiment in hospital, calculated values were not agreed with experimental values. It might be three possible reasons as the cause of this deference, such as irradiation energy, calculation procedure and cross section data. Obtained data of this work, calculated and experimental values were good agreement with each other within one order. In this work, we used KAERI dataset of photonuclear reaction instead of JENDL. Therefore, it was found that the photonuclear cross section data of light elements are most important for yield calculation in these reactions. Conclusion: Further improvement for calculation using a new dataset JENDL/PD-2015 and considering electron energy spreading will be needed.